ML112650303
| ML112650303 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 09/21/2011 |
| From: | NRC/RGN-II |
| To: | Duke Energy Carolinas |
| References | |
| Download: ML112650303 (79) | |
Text
Appendix C Job Performance Measure Form ES-C-i Worksheet JPM Ala SRO 2011 Admin
NUREG 1021, Revision 9
Appendix C Page 2 of 13 Form ES-C-i Job PerformanceMeasure Worksheet Facility:
McGuire Task No.:
Task
Title:
2011 Admin
Reference:
GK/A 2.1.7 (4.4/4.7)
Examinee:
NRC Examiner:
Facility Evaluator:
Date:
Method of testing:
Simulated Performance:
Actual Performance:
X Classroom X
Simulator Plant READ TO THE EXANIINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:
The Unit I OAC failed and is not operating.
The vendor is being consulted concerning repairs.
It is estimated it will take approximately 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> to complete repairs.
The crew has implemented PT/IJA/4600/021A (Loss of Operator Aid Computer while in Mode 1) and completed through step 12.13.
Unit I is at 99% power and all Power Range Instruments are OPERABLE.
Task Standard:
The operator will calculate the QPTR (See Attached Key) and determine that the QPTR Technical Specification has been exceeded; Then identify the required TS ACTION (i.e. Power must be reduced to at least 94%, and ACTIONS a.2 through A.7 must be taken).
Required Materials:
Calculator McGuire Technical Specifications General
References:
PT/1/A14600/021A (Loss of Operator Aid Computer while in Mode 1),
Rev 36 OP/1/A/6100/022 (MNS Unit #1 Data Book)
McGuire Technical Specifications (LCO 3.2.4/Amendment 184/166) 2011 Admin-JPM Ala SRO NUREG 1021, Revision 9
Appendix C Page 3 of 13 Form ES-C-i Job Performance Measure Worksheet Handouts:
PTI1IAI4600IO21A (Loss of Operator Aid Computer while in Mode 1) marked up through step 12.13.
Detector Currents (Page 12 of 13 of this JPM)
OP/1/A/6100/022 (MNS Unit #1 Data Book), Enclosure 4.3, Table 2.2 (Excore Currents and Voltages Correlated to 100% Full Power at Various Axial Offsets)
McGuire Technical Specifications (Available)
Initiating Cue:
The CRS has directed you to calculate QPTR in accordance with Step 12.14 of PT/11A14600121A (Loss of Operator Aid Computer whNe in Mode 1), and identify any applicable Technical Specification required ACTION.
Time Critical Task:
NO Validation Time:
25 minutes 2011 Admin-JPMA1aSRO NUREG 1021, Revision9
Appendix C Page 4 of 13 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)
Provide Candidate with Initial ConditionslCue (Last Page of this JPM), the Detector Currents (2 to last Page of this JPM), handout PTIIIAI4600IO2IA marked up through step 12.13, and MNS Unit I Data Book Table 2.2 (Cycle 21).
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT (Step 12.14)
The operator determines from initial conditions QPTR IF QPTR Alarm inoperable Alarm is inoperable, Unit I AND greater than 50%
is at 100% power and all RTP, perform the following:
PR channels are operable.
(Step 12.14.1)
If all Power Range (PR)
Operator proceeds to channel inputs to QPTR 3.5 (Calculation operable, calculate QPTR Sheet for Quadrant Power on Enclosurei3.5 Tilt) Part A.
(Calculation Sheet for Quadrant Power Tilt) Part A within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter until QPTR Alarm operable.
2 (Enclosure 13.5 Part A)
The operator enters the current Date and Time at Complete the Form the top of the form.
2011 Admin
- JPM Ala SRO NUREG 1021, Revision 9
Appendix C Page 5 of 13 Form ES-C-i PERFORMANCE INFORMAT1orT STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 3 (Enclosure 13.5 Part A)
The operator records the Measured Current - From correct amperage reading NI cabinets current meter for each detector (From the (located on respective PRB Handout provided) in the Drawers). Ensure Detector Measured Current row for Milliamp Range Switches each of the eight (8) are in 0.5 position and detectors as follows:
read 0-500 microamp scale.
PR.41A = 295 PR-41B = 304 PR-42A 299 PR-42B = 327 PR-43A = 299 PR-43B = 315 PR-44A = 285 PR-44B = 304
- 4 (Enclosure 13.5 Part A)
The operator locates Calibration Current
- From OP/1/A/6100/022, most recent calibration data.3, Table 2.2, using 0 Incore Axial Offset Excore Currents and Current in Data Book, Table Voltages Correlated to 2.2 (IT for detector A, 100% Full Power at Various IB for detector B).
Axial Offsets.
The operator records the correct amperage reading for each detector (Table 2.2) in the Calibration Current row for each of the eight (8) detectors as follows:
PR-41A = 142.0 PR-41B = 155.3 PR-42A = 150.0 PR-42B = 160.3 PR-43A = 145.0 PR-43B = 162.4 PR-44A = 137.5 PR-44B = 158.1 2011 Admin
- JPM Al a SRO NUREG 1021, Revision 9
Appendix C Page 6 of 13 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 5 (Enclosure 13.5 Part A)
The operator correctly Relative Flux (RF)
Divide calculates the average RF line 1 by line 2 to calculate and records the in the Relative Flux (RE) for each Relative Flux (RE) row for upper (A) and lower (B) each of the eight (8) detector.
detectors as follows:
PR-41A = 295/1 42.0 = 2.08 PR-41B = 304/1 55.3 1.96 PR-42A = 299/1 50.0 = 1.99 PR-42B = 327/1 60.3 = 2.04 PR-43A 299/1 45.0 = 2.06 PR-43B = 315/1 62.4 = 1.94 PR-44A = 285/i 37.5 = 2.07 PR-44B = 304/i 58.1 = 1.92
- 6 (Enclosure 13.5 Part A)
The operator records the Quadrant Power Tilts:
RE of each of the four (4) A Calculate by dividing each detectors and calculates the upper relative flux by the Avg RF of A Detectors as average upper relative flux follows:
and dividing each lower relative flux by the average (2.08÷1.99+2.06÷2.07)14 =
2.05 lower relative flux.
Avg RF of A Detectors
- 7 (Enclosure 13.5 Part A)
The operator records the Quadrant Power Tilts:
RE of each of the four (4) B Calculate by dividing each detectors and calculates the upper relative flux by the Avg RF of B Detectors as average upper relative flux follows:
and dividing each lower relative flux by the average (1.96+2.04+1.94÷1.92)14 =
1.97 lower relative flux.
Avg RE of B Detectors 2011 Admin-JPM Ala SRO NUREG 1021, Revision 9
Appendix C Page 7 of 13 Form ES-C1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 8 (Enclosure 13.5 Part A)
The operator calculates the Quadrant Power Tilts:
PR-41A Tilt as follows:
Calculate by dividing each 2.0812.05 = 1.01 +.01 upper relative flux by the
average upper relative flux And records this value.
and dividing each lower relative flux by the average lower relative flux.
PR-41A Tilt
- 9 (Enclosure 13.5 Part A)
The operator calculates the Quadrant Power Tilts:
PR-41 B Tilt as follows:
Calculate by dividing each 1.96I1.97 = 0.99 +.01 upper relative flux by the
average upper relative flux And records this value.
and dividing each lower relative flux by the average lower relative flux.
PR-41 B Tilt
- 10 (Enclosure 13.5 Part A)
The operator calculates the Quadrant Power Tilts:
PR-42A Tilt as follows:
Calculate by dividing each 1.9912.05 = 0.97 +.01 upper relative flux by the
average upper relative flux And records this value.
and dividing each lower relative flux by the average lower relative flux.
PR-42A Tilt
- 1 1 (Enclosure 13.5 Part A)
The operator calculates the Quadrant Power Tilts:
PR-42B Tilt as follows:
Calculate by dividing each 2.04!1.97 = 1.04 +.01 upper relative flux by the
average upper relative flux And records this value.
and dividing each lower relative flux by the average lower relative flux.
PR-42B Tilt 2011 Admin
- JPM Ala SRO NUREG 1021, Revision 9
Appendix C Page 8 of 13 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- i2 (Enclosure 13.5 Part A)
The operator calculates the Quadrant Power Tilts:
PR-43A Tilt as follows:
Calculate by dividing each 2 0612 0
+
upper relative flux by the
average upper relative flux And records this value.
and dividing each lower relative flux by the average lower relative flux.
PR-43A Tilt
- 13 (Enclosure 13.5 Part A)
The operator calculates the Quadrant Power Tilts:
PR-43B Tilt as follows:
Calculate by dividing each 1 94/1 97
+
upper relative flux by the
average upper relative flux And records this value.
and dividing each lower relative flux by the average lower relative flux.
PR-43B Tilt
- 14 (Enclosure 13.5 Part A)
The operator calculates the Quadrant Power Tilts:
PR-44A Tilt as follows:
Calculate by dividing each 2 0712 0
+
upper relative flux by the
average upper relative flux And records this value.
and dividing each lower relative flux by the average lower relative flux.
PR-44A Tilt
- 15 (Enclosure 13.5 Part A)
The operator calculates the Quadrant Power Tilts:
PR-44B Tilt as follows:
Calculate by dividing each 1 92/1 97 0 97 + 01 upper relative flux by the
average upper relative flux And records this value.
and dividing each lower relative flux by the average lower relative flux.
PR-44B Tilt 2011 Admin
- JPM Al a SRO NUREG 1021, Revision 9
Appendix C Page 9 of 13 Form ES-C-i PERFORMANCE INFORMATiON STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 16 (Technical Specification The operator determines 3.2.4) The QPTR shall be that a quadrant is >1.02 and
< 1.02.
refers to LCO 3.2.4.
The operator determines that power must be reduced (ACTION A.1) to at least 94% (Highest QPTR is 1.04 on PR-42B; Reduce 3%
from RTP (100%) for each 1% of QPTR> 1.02 (1.04-1.02 0.02 x 3% RTP xlOO%
QPTR/RTP)).
The operator determines that ACTION A.2, A.3, A.4, A.5, A.6 and A.7 must be completed within the required COMPLETION TIME.
Terminating Cue:
Evaluation on this JPM is complete.
STOP TIME:
2011 Admin
- JPM Ala SRO NUREG 1021, Revision 9
Appendix C Page 10 of 13 Form ES-C-i VEF[OAT[O OF MLTlON Job Performance Measure No.:
2011 Admin
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result:
SAT UNSAT Examiners Signature:
Date:
2011 Admin-JPMA1aSRO NUREG 1021, Revision 9
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Appendix C Form ES-C-i JPM CUE SKEET The following Detector Currents are observed on the NI cabinet current meters:
NI-41 detector:
A (left) 295 B (right) 304 NI-42 detector:
A (left) 299 B (right) 327 NI-43 detector:
A (left) 299 B (right) 315 Nl-44 detector:
A (left) 285 B (right) 304 NUREG 1021, Revision 9
Appendix C Form ES-C-i JPMCUES[-tEET Initial Conditions:
The Unit 1 OAC failed and is not operating.
The vendor is being consulted concerning repairs.
It is estimated it will take approximately 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> to complete repairs.
The crew has implemented PTI1IAI4600/021A (Loss of Operator Aid Computer while in Mode 1) and completed through step 12.13.
Unit 1 is at 99% power and all Power Range Instruments are OPERABLE.
INITIATING CUE:
The CRS has directed you to calculate QPTR in accordance with Step 12.14 of PT/iIAI4600/21A (Loss of Operator Aid Computer while in Mode 1), and identify any applicable Technical Specification required ACTION.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-i Worksheet JPM Aib SRO 201 i Admin
NUREG i 021, Revision 9
Appendix C Page 2 of 8 Form ES-C-i JOb Perf mane ftituf WOrksheet Facility:
McGuire Task No.:
Task
Title:
Calculate Reactor Vessel Head JPM No.:
2011 Admin
- JPM Al b Venting Time SRO K/A
Reference:
GK/A 2.1.25 (3.9/4.2)
Examinee:
NRC Examiner:
Facility Evaluator:
Date:
Method of testing:
Simulated Performance:
Actual Performance:
X Classroom X
Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:
McGuire Unit 1 is in a Post-Accident situation.
You are a Licensed Operator available in the Operational Support Center (OSC).
EP/1/A/5000/FR-I.3 (Response to Voids in Reactor Vessel) has been implemented and completed through step 20.a.
The following conditions exist:
Containment Pressure 7.2 psig Lower Containment Temperature 190°F Containment H2 Concentration 2.9 %
NC Pressure 550 psig Task Standard:
The Reactor Vessel Head venting time calculated to fall between 1.74 and 1.85 minutes.
Required Materials:
Calculator General
References:
EP/1/A15000/FR-I.3 (Response to Voids in the Reactor Vessel), Rev 9 Handouts:
EP/1/A/5000/FR-I.3 (Response to Voids in the Reactor Vessel) (Allowable H2 Venting Time) 2011 Admin-JPMAIbSRO NUREG 1021, Revision9
Appendix C Page 3 of 8 Form ES-C-i Job Performance Measure Worksheet Initiating Cue:
You have been directed to calculate maximum venting time per Enclosure I, (Allowable H2 Venting Time) of EPIIIAI5000IFR-l.3, (Response to Voids in Reactor Vessel).
Time Critical Task:
NO Validation Time:
15 minutes 2011 Admin
- JPM Al b SRO NUREG 1021, Revision 9
Appendix C Page 4 of 8 Form ES-C-i PfRFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)
Provide Candidate with Initial ConditionslCue (Last Page of this JPM), and Handout EPII IAI5000IFR-l.3, Enclosure 1.
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- i (Step 1) Calculate A The operator calculates A A = 9,500 (x) (P+14.7) (x) 492 9,500 (x) (7.2+14.7) (x) 492 14.7 (T+460) 14.7 (190+460)
Where:
P = 7.2 as stated in Initial Conditions.
P =
Containment T = 190 as stated in Initial pressure (PSIG)
Conditions.
T =
Lower containment This equals ave. temp (F) 9,500 1.49 x 0.76 and this equals:
A=
A= 10757.80
- 2 (Step 2) Calculate B The operator calculates B B=(3-H)(x)A (32.9)x10757.80=
where H = 2.9 as stated in Initial Conditions.
H =
Containment H-2 A = Calculated Value in Concentration (%).
Step 1.
B =
(0.1) x (10757.80) =
B = 1075.78 2011 Admin - JPM Aib SRO NUREG 1021, Revision 9
Appendix C Page 5 of 8 Form ES-C-i PERFOIMANCE[NFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 3 (Step 3) Determine C from The operator uses Curve on the curve for the current NC Page 2 of 2 of Enclosure 1, system pressure and determines C to equal 600 +/-20 using curve
- 4 (Step 4) Calculate T The operator calculates T T = B/C =
Venting Time 1075.78 in minutes 600 T=
/
B=Calculated Value in Step 2.
T minutes C = Value obtained from Curve in Step 3.
1.79 minutes (Acceptable range of I.74 1.85 minutes)
Terminating Cue:
Evaluation on this JPM is complete.
STOP TIME:
2011 Admin
- JPM Al b SRO NUREG 1021, Revision 9
Appendix C Page 6 of 8 Form ES-C-i VERIFICATION OF COMPLET[O Job Performance Measure No.:
2011 Admin
- JPM Ai b SRO Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result:
SAT UNSAT Examiners Signature:
Date:
2011 Admin-JPMAIbSRO NUREG 1021, Revision 9
Appendix C Page 7 of 8 Form ES-C-i VERIFICATION OFCOMPLETION KEY:
A = 9,500 (x) (P+14.7) (x) 492 14.7 (T+460)
A=9,500(x) (7.2+14.7)(x) 492 14.7 (190+460)
A = 9,500 x 1.49 x 0.76 = 10757.80 B = (3
- H) (x) A B
(32.9) x 10,757.80 B = (0.1) x (10,757.80) = 1075.78 C = Using Enclosure 1 Graph for NC System Pressure of 350 psig = 600+/-20 SCFM Venting Time in minutes (T) = B/C =1075.78
= 1.74-1.85 minutes 600+/-20 (Acceptable range of 1.74 1.85 minutes) 2011 Admin
- JPM Aib SRO NUREG 1021, Revision 9
Appendix C Form ES-C-i MCUESHEET INITIAL CONDITIONS:
McGuire Unit 1 is in a Post-Accident situation.
You are a Licensed Operator available in the Operational Support Center (OSC).
EPI1IAI5000IFR-l.3 (Response to Voids in Reactor Vessel) has been implemented and completed through step 20.a.
The following conditions exist:
Containment Pressure 7.2 psig Lower Containment Temperature 190°F Containment H2 Concentration 2.9 %
NC Pressure 550 psig INITIATING CUE:
You have been directed to calculate maximum venting time per Enclosure I (Allowable H2 Venting Time) of EP/1/A15000/FR-l.3, (Response to Voids in Reactor Vessel).
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-i Worksheet JPMA2SRO 2011 Admin
NUREG 1021, Revision 9
Appendix C Page 2 of 10 Form ES-C-i Job PerfOrmaroe Muf WOr1<ht Facility:
McGuire Task No.:
Task
Title:
Perform a Thermal Margin JPM No.:
2011 Admin
- JPM A2 Determination SRO K/A
Reference:
GKIA 2.2.12 (3.9)
Examinee:
NRC Examiner:
Facility Evaluator:
Date:
Method of testing:
Simulated Performance:
Actual Performance:
X Classroom X
Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:
Unit I was shutdown 24 days ago for a mid-cycle outage after 200 days of operation.
Unit I is currently in Mode 5.
No Core Offload will occur.
The NC system is 145F with A Train ND in service.
Preparations are being made to lower NC system level to 9 inches above Hot Leg Centerline per Enclosure 4.1 (Draining the NC System) of OPIIIAI6I 00/SD-20 (Draining the NC System).
Task Standard:
The operator will complete Attachment 12.6 (Thermal Margin Determination) of OMP 5-8 (Shift Supervision Turnovers) with a new thermal margin calculated and documented on Attachment 12.7 (Shutdown Assessment Status) and on MC-6/MLOG, as well as make the required notifications to the CCC and STA.
Required Materials:
None General
References:
OP/1/A16100/SD-20 (Draining the NC System), Rev 40 OMP 5-8 (Shift Supervision Turnovers), Rev 44 OP/i/A/6i00/22 (Core Data Book), Cycle 21 2011 Admin
- JPM A2 SRO NUREG 1021, Revision 9
Appendix C Page 3 of 10 Form ES-C-i Job Performance Measure Worksheet Handouts: 2.6 (Thermal Margin Determination) of OMP 5-8 (Shift Supervision Turnovers). 2.7 (Shutdown Assessment/Status) of OMP 5-8 (Shift Supervision Turnovers).
OP/i 1A161 00/22 (Core Data Book), Cycle 21, Enclosure 4.3, Section 2.10 (Thermal Margin Curves at Various Reactor Vessel Levels).
Initiating Cue:
Complete Attachment 12.6 of OMP 5-8 (Shift Supervision Turnovers) to determine the new thermal margin with NC system level at 9 inches above Hot Leg Centerline and make the appropriate notifications.
Record the following:
New Thermal Margin Personnel to be notified:
Time Critical Task:
NO Validation Time:
22 minutes 2011 Admin
- JPM A2 SRO NUREG 1021, Revision 9
Appendix C Page 4 of 10 Form ES-C-i PERFORMANCE INFORMATiON (Denote Critical Steps with an asterisk*)
Provide Candidate with Initial ConditionslCue (Last Page of this JPM), and the three (3) identified Handouts.
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT (Attachment 12.6)
The operator places a Applicable to:
check in the Unit I checkbox.
Unit 1 Unit 2 2011 Admin
- JPM A2 SRO NUREG 1021, Revision 9
(Attachment 12.6, Step 1)
Refer to OP/i (2)/A/61 00/22, Unit 1 (2) Databook,.3, Section 2.10 Thermal Margin Curves, to determine appropriate section and/or curve to use.
SECTION/CURVE USED The operator obtains the Core Data Book and locates Section 2.10.
The operator recognizes that since the Loops are drained and the Vessel Head has NOT been removed, the Curves of Section 2.10.1 are applicable.
The operator determines that from the Initial conditions given, Enclosure 4.3 Section 2.10.1 A is to be used, and records this, placing their initial in the appropriate Block.
Using 2.10.1 A Curve, the operator intersects the point of 24 days after shutdown and the 160°F temperature Curve, and determines that the new Thermal Margin is
.36+/-.02 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or 21.6 +/-1.2 minutes.
NOTE: The operator may use 2.10.1 A (1) Curve.
If so, the operator intersects the point of 24 days after shutdown and the 160°F temperature Curve, and determines that the new Thermal Margin is 22 +/-1 minutes.
Appendix C Page 5 of 10 Form ES-C-i PERFORMANCE1NFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT INITIAL________
2011 Admin
- JPM A2 SRO NUREG 1021, Revision 9
Appendix C Page 6 of 10 Form ES-C-i PERFORMANCEirFORMAT1ON STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 3
(Attachment 12.6, Step 2)
The operator records the Document thermal margin date in the chart on time and maximum NC 2.6.
Temperature allowed (for curve used) in the table The operator records the below and initial, time in the chart on 2.6.
The operator records 21.6
+/-1.2 minutes in the Thermal Margin MIN block on the chart on Attachment 12.6.
The operator records 160°F in the Max NC Temp °F block on the chart on 2.6.
4 (Attachment 12.6, Step 3)
Communicate Thermal Margin as follows:
The operator records 21.6
+/-1.2 minutes in the (Attachment 12.6, Step 3.a)
Thermal Margin Column Write thermal margin time TM Minutes block on and max NC Temp on the 2.7.
Shutdown Assessment/Status The operator records 160°F (Attachment 12.7). Include in the Thermal Margin any data Book 4.3 Section Column Max NC Temp 2.10 support parameters block on Attachment 12.7.
(SIG Lvls, Pzr Lvl, etc.)
Initial in Table below.
The operator records 9 in the Thermal Margin Column NCS Level block on 2.7.
The operator places their initial in the Thermal Margin Data Written on Shutdown Assessment/Status (Attachment 12.7) block on the chart on Attachment 12.6.
2011 Admin-JPMA2SRO NUREG 1021, Revision9
Appendix C Page 7 of 10 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 5 (Attachment 12.6, Step 3.b)
The operator contacts the Notify the Containment CCC and notifies that TM is Closure Coordinator (CCC) 21.6 +/-1.2 minutes.
of the thermal margin time determined. Initial in the Cue:
table below.
The Containment Closure Coordinator has been notified.
The operator places their initial in the CCC Notified block on the chart on 2.6.
- 6 (Attachment 12.6, Step 3.c)
Notify the Shift Technical The operator contacts the Advisor (STA) of the STA and notifies that TM is thermal margin time 21.6 +/-1.2 minutes.
determined. Initial in the table below.
I Cue:
The STA has been notified.
The operator places their initial in the STA Notified block on the chart on 2.6.
2011 Admin
- JPM A2 SRO NUREG 1021, Revision 9
Appendix C Page 8 of 10 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 7
(Attachment 12.6, Step 3.d)
The operator directs the Write thermal margin time OATC to write 21.6 +/-t2 on MC-6 and update minutes in the TM Block on MLOG. Initial in the table MC-6, and enter into below.
MLOG.
Cue:
MC-61MLOG has been updated.
The operator places their initial in the Thermal Margin Time Written on MC-6 and MLOG block on the chart on Attachment 12.6.
Terminating Cue:
Evaluation on this JPM is complete.
STOP TIME:
2011 Admin-JPMA2SRO NUREG 1021, Revision 9
Appendix C Page 9 of 10 Form ES-C-I VERIFICATION OF COMPLETION Job Performance Measure No.:
2011 Admin
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result:
SAT UNSAT Examiners Signature:
Date:
2011 Admin-JPMA2SRO NUREG 1021, Revision 9
Appendix C Form ES-C-i JPM CUE SHEET INITIAL CONDITIONS:
Unit 1 was shutdown 24 days ago for a mid-cycle outage after 200 days of operation.
Unit I is currently in Mode 5.
No Core Offload will occur.
The NC system is 145°F with A Train ND in service.
Preparations are being made to lower NC system level to 9 inches above Hot Leg Centerline per Enclosure 4.1 (Draining the NC System) of OP/1/A16i00/SD-20 (Draining the NC System).
INITIATING CUE:
Complete Attachment 12.6 of OMP 5-8 (Shift Supervision Turnovers) to determine the new thermal margin with NC system level at 9 inches above Hot Leg Centerline and make the appropriate notifications.
Complete Attachment 12.6 of OMP 5-8 (Shift Supervision Turnovers) to determine the new thermal margin with NC system level at 9 inches above Hot Leg Centerline and make the appropriate notifications.
Record the following:
New Thermal Margin Personnel to be notified:
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-i Worksheet JPMA3SRO 2011 Admin
NUREG 1021, Revision 9
Appendix C Page 2 of 9 Form ES-C-i Job Performance Measure Worksheet Facility:
McGuire Task No.:
Task
Title:
Take On-Site Protective Actions JPM No.:
Exam 2011 Admin During a General Emergency JPM A3 SRO K/A
Reference:
GKIA 2.3.4 (3.7)
Examinee:
NRC Examiner:
Facility Evaluator:
Date:
Method of testing:
Simulated Performance:
Actual Performance:
X Classroom X
Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:
With Unit I shutting down due to failed fuel causing high NC System Activity, a LOCA Outside of Containment occurred.
A Site Assembly is in progress in accordance with Enclosure 4.3 of RP/0/A15700/01 I (Conducting a Site Assembly, Site Evacuation or Containment Evacuation), and all personnel have NOT been accounted for.
An RP Technician reports that an operator working with him in the 695 pipe chase has fallen and is severely injured. He has moved the injured person to an area that is somewhat shielded. Due to rapidly increasing dose rates, the RP Technician leaves to get help. He believes the injuries are life threatening. He also stated that the individual could be retrieved but it would take two people to do so.
The OSM has initiated and completed the immediate and subsequent actions of Enclosure 4.1 of RP/0/A/5700/004 (General Emergency).
RP has been contacted and estimates it will take at least ten minutes to retrieve the victim. Auxiliary Building Area Radiation Monitors indicate extremely high radiation levels.
Dose rates at the area needing access are greater than 500 Rem/Hr.
Task Standard:
Select and dispatch two rescuers (Smith and Shelly) by completing.4 of RP/0/A/5700/004 (General Emergency).
2011 Admin
- JPM A3 SRO NUREG 1021, Revision 9
Appendix C Page 3 of 9 Form ES-C-i Job Performance Measure Worksheet Required Materials:
Calculator General
References:
RP101A157001004 (General Emergency), Rev 25 RP101A15700101 1 (Conducting a Site Assembly, Site Evacuation or Containment Evacuation), Rev 14 RP101A15700129, RP101A15700129 (Notification of Off-Site Agencies From the Control Room), Rev 10 OMP 2-2 (Conduct of Operations), Rev 54 Handouts:
RP101A157001004, General Emergency, marked up as follows:
Section 2 immediate actions are complete.
- .1 actions are complete.
Section 3 subsequent actions complete through Step 3.8.1.
List of Available Rescuers Initiating Cue:
As the OSM, evaluate, and take on-site Protective Actions in accordance with Step 3.8.2 and 3.8.3 of RPIO/A15700/004 (General Emergency).
Time Critical Task:
NO Validation Time:
15 minutes 2011 Admin
- JPM A3 SRO NUREG 1021, Revision 9
Appendix C Page 4 of 9 Form ES-C-I PFOMANCNFORMATlON (Denote Critical Steps with an asterisk*)
Provide Candidate with Initial ConditionslCue (Last Page of this JPM), and Handout:
RP101A157001004 marked up as described, and the List of Available Rescuers.
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT (RPO4/Step 3.8.2) IF a The operator recognizes situation is immediately from initial conditions that hazardous to life or valuable Dose rates at the area property exists, evaluate needing access is greater potential dose rates by one than 500 Rem/Hr.
of the following methods:
(Step 3.8.2.a) Contact RP Shift at Ext. 4282.
2 (Step 3.8.2.b) Assess area The operator recognizes monitors.
from initial conditions that Dose rates at the area needing access is greater than 500 Rem/Hr.
The operator determines that rescuers will need to be authorized to receive Emergency Exposure Dose Limits.
3 (Step 3.8.3) Complete The operator reviews List of.4 (Request for Available Rescuers in Emergency Exposure), prior Control Room and to dispatch of emergency determines qualification of workers if emergency potential rescuers.
situation precludes documentation.
- 4 (Enclosure 4.4.a)
The operator determines Request for Emergency that Casey cannot be Exposure dispatched as a rescuer (Declared pregnancy) 2011 Admin-JPMA3SRO NUREG 1021, Revision 9
Appendix C Page 5 of 9 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 5 (Enclosure 4.4.c) Only on a Operator determines that volunteer basis to persons Blade cannot be dispatched fully aware of the risks as a rescuer (Does NOT involved. All factors being Volunteer).
equal, select volunteers above the age of 45 and Operator determines that those who normally receive Mack cannot be dispatched little exposure.
as a rescuer (Has too much Lifetime Exposure).
Operator determines that Leavy cannot be dispatched as a rescuer (Only STA OMP 2-2 requires her in Control Room).
Operator determines that Baylor cannot be dispatched as a rescuer
(< 45 years Old).
6 (Enclosure 4.4) Request for Emergency Exposure The operator selects Smith and Shelly as rescuers, and completes Enclosure 4.4.
The operator enters the following information on.4 for Smith:
RPBadge#-12579 Name Smith Age52 Employer Duke The operator enters the following information on.4 for Shelly:
RPBadge#-12456 Name Shelly Age48 Employer Duke 2011 Admin-JPMA3SRO NUREG 1021, Revision 9
Appendix C Page 6 of 9 Form ES-C-i FERFOlMANCElNFORMA11ON STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 6
The operator has Smith (Contd) and Shelly Read and Sign.4.
Cue:
After having selected rescuers sign Enclosure 4.4, indicate that each has signed.
Cue:
If Operator seeks concurrence from RPM for authorization of Emergency Exposure Limits, indicate RPM Bob Smith has concurred.
The operator signs.4 indicating that they approve the Emergency Exposure Authorization.
Terminating Cue:
Evaluation on this JPM is complete.
STOP TIME:
2011 Admin
- JPM A3 SRO NUREG 1021, Revision 9
Appendix C Page 7 of 9 Form ES-C-i VER[FfCATiON OF COMPLETiON Job Performance Measure No.:
2011 Admin
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result:
SAT UNSAT Examiners Signature:
Date:
2011 Admin
- JPM A3 SRO NUREG 1021, Revision 9
Appendix C Form ES-C-i JPM CUE SHEET List of Available Rescuers in Control Room:
RP Name Gender!
Job Employer Current Lifetime Special Status Badge Age Assignment Exposure Exposure (yr)
Would prefer not to 12345 Blade Male!
Maintenance Duke 1800 mr 5.2 R go! Reports good 49 physical health 12456 Shelly Female!
Engineer Duke 45 mr 400 mr Volunteers! Reports 48 good physical health 12567 Mack Male NEC Duke 125 mr 35.4 R Volunteers! Reports
/45 good physical health 12579 Smith Male!
Training Duke 6 mr 1400 mr Volunteers!Reports 52 Supervisor good physical health 12110 Casey Female!
Security Duke 10 mr 65 mr Declared 32 Supervisor PregnantNolunteers!
Reports good physical health 12238 Leavy Female!
STA Duke 4 mr 120 mr Volunteers!Only STA 46 qualified individual in Control Room!
Reports good physical health.
12198 Baylor Male!
U2 BOP Duke 78 mr 1.7 R Volunteers! Reports 34 good physical health NUREG 1021, Revision 9
Appendix C Form ES-C-I JPM CUE SHEET INITIAL CONDITIONS:
With Unit 1 shutting down due to failed fuel causing high NC System Activity, a LOCA Outside of Containment occurred.
A Site Assembly is in progress in accordance with Enclosure 4.3 of RPIOIAI5700IO1 1 (Conducting a Site Assembly, Site Evacuation or Containment Evacuation), and all personnel have NOT been accounted for.
An RP Technician reports that an operator working with him in the 695 pipe chase has fallen and is severely injured. He has moved the injured person to an area that is somewhat shielded. Due to rapidly increasing dose rates, the RP Technician leaves to get help. He believes the injuries are life threatening. He also stated that the individual could be retrieved but it would take two people to do so.
The OSM has initiated and completed the immediate and subsequent actions of Enclosure 4.1 of RP101A157001004 (General Emergency).
RP has been contacted and estimates it will take at least ten minutes to retrieve the victim. Auxiliary Building Area Radiation Monitors indicate extremely high radiation levels.
Dose rates at the area needing access are greater than 500 Rem/Hr.
INITIATING CUE:
As the OSM, evaluate, and take on-site Protective Actions in accordance with Step 3.8.2 and 3.8.3 of RP/0/A15700/004 (General Emergency).
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ESC-1 Worksheet JPMA4SRO 2011 Admin
NUREG 1021, Revision 9
Appendix C Page 2 of 6 Form ES-C-i Jb PErrrrnane Meure WrksI1Eet Facility:
McGuire Task No.:
Task
Title:
Classify an Emergency Event JPM No.:
2011 Admin
Reference:
GK/A 2.4.41 (2.9/4.6)
Examinee:
NRC Examiner:
Facility Evaluator:
Date:
Method of testing:
Simulated Performance:
Actual Performance:
X Classroom X
Simulator Plant EXAMINER NOTE:
The operator will be given a timeline of events that span a few hours, and asked to classify the event per RPIOIAI5700I000, Classification of Emergency, at two (2) different times during the event.
READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:
A plant event is in progress on Unit 1.
Task Standard:
The operator will declare a Site Area Emergency based on 4.1.S.3, Loss of Containment AND Loss or Potential Loss of Any other Barrier.
Required Materials:
Blank Copies of RP/0/A15700/000, Enclosure 4.1, Fission Product Barrier Matrix.
General
References:
RP/0/A/5700/000 (Classification of Emergency) Rev 16 AP/1/A15500/18 (High Activity in Reactor Coolant), Rev 4 AP/1/A15500/10 (NC System Leakage Within the Capacity of Both NV Pumps), Rev 22 EP/i/A/5000/E-0 (Reactor Trip or Safety Injection), Rev 31 EP/1/A/5000/E-2 (Faulted Steam Generator Isolation), Rev 9 2011 Admin
- JPM A4 SRQ NUREG 1021, Revision 9
Appendix C Page 3 of 6 Form ES-C-i Job Performance Measure Worksheet EPI1IAI5000IE-3 (Steam Generator Tube Rupture), Rev 19 OMP 4-3 (Use of Abnormal and Emergency Procedures), Rev 32 McGuire Technical Specifications Handouts:
RP/O/A/5700/000 (Classification of Emergency)
McGuire Technical Specifications lnftiating Cue:
Classify the Event in accordance with RPIOIA/5700/000 (Classification of Emergency).
Time Critical Task:
YES 15 minute Validation Time:
15 minutes 2011 Admin
- JPM A4 SRO NUREG 1021, Revision 9
Appendix C Page 4 of 6 Form ES-C-i PEORMANCElNFORMAON (Denote Critical Steps with an asterisk*)
Provide Candidate with Last Page of this JPM.
START TIME:
Terminating Cue:
Evaluation on this JPM is complete.
TIME CRITICAL STOP TIME:
- 1 (OMP 4-3, Steps 7.20.1/7.20.1.1-2) OSM Responsibilities The operator enters RPIOIAI5700J000, Step 2.1 and determines that the plant was in Mode 1 at the start of the event.
Assume role of Emergency Coordinator upon activation of the Emergency Plan until properly relieved by the Station Manager.
Emergency Classification is done properly and in a The operator reviews.1, and determines a Loss of Containment exists, based on 4.i.C.4, SG Secondary Side Release With Primary-to-Secondary Leakage.
timely manner.
Time = 0349 The operator records 3 points for the loss of the Containment Barrier in Table on Page 2 of 5 of Enclosure 4.1.
The operator reviews.1, and determines a Loss of NCS exists, based on 4.1.N.3, SG Tube Rupture.
The operator records 5 points for the Loss of the NCS barrier in Table on Page 2 of 5 of.1.
NOTE: The operator declaring an SAE is Critical.
With a total of 8 points, the operator determines that a Site Area Emergency exists, based on 4.1.S.3. Loss of Containment AND Loss or Potential Loss of Any other Barrier.
The operator reviews Enclosures 4.2 through 4.7.
2011 Admin-JPMA4SRO NUREG 1021, Revision 9
Appendix C Page 5 of 6 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.:
2011 Admin
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result:
SAT UNSAT Examiners Signature:
Date:
2011 Admin-JPMA4SRO NUREG 1021, Revision 9
Appendix C Form ES-C-I JPMCUESF-IEET Event Timeline Initial Conditions:
0100 Unit 1 and Unit 2 are in Mode 1 at 100% power.
0100 The following Radiation Monitors come into alarm simultaneously:
1 EMF-48, Reactor Coolant Rad Hi IEMF-18, Reactor Coolant Filter 1A o
1 EMF-I 9, Reactor Coolant Filter I B 0101 The crew entered and completed AP/1IA/5500/18 (High Activity in Reactor Coolant).
0156 Chemistry has determined that the increased radiation levels are due to fuel failure, and report that the Dose Equivalent Iodine levels have stabilized at 0.7 pc/gm.
0215 Station management has directed that Unit 1 be brought to Hot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
0302 During the shutdown, a 20 gpm tube leak develops on the B Steam Generator, and the crew enters AP/1/A15500/I0 (NC System Leakage Within the Capacity of Both NV Pumps).
0307 An Unusual Event was declared based on 4.I.U.2L Loss of Containment.
0334 The B MSIV inadvertently closes and the reactor trips. The crew enters EP/1/A15000/E-0 (Reactor Trip or Safety Injection).
0335 Based on slowly decreasing Pzr pressure, the crew manually actuates Safety Injection.
0340 The crew receives a report that a Steam Generator Safety valve on the B Steam Generator has lifted and stuck partially open causing steam to issue into the sky.
0344 The crew transitions to EP/1/A15000/E-2 (Faulted Steam Generator Isolation).
0348 The crew observes SI flow at 400 gpm, Pzr level stable at 12%,
and the B Steam Generator Narrow Range Level increasing with CA flow shutoff.
0349 The crew isolates the B Steam Generator and transitions to EP/1/A/5000/E-3 (Steam Generator Tube Rupture). The Safety valve on the B Steam Generator is still stuck partially open.
INITIATING CUE:
Update Event classification in accordance with RP/0/A/5700/000 (Classification of Emergency).
This is a Time Critical JPM Classification:
EAL #:
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-I Worksheet JPMAIaRO 2011 Admin
NUREG 1021, Revision 9
Appendix C Page 2 of 14 Form ES-C-i Job PerlOrmanoe MesureWorksheet Facility:
McGuire Task No.:
Task
Title:
Perform a Manual Shutdown Margin JPM No.:
2011 Admin
Reference:
GK/A2.1.20 (4.6)
Examinee:
NRC Examiner:
Facility Evaluator:
Date:
Method of testing:
Simulated Performance:
Actual Performance:
X Classroom X
Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:
Unit I was shutdown to Mode 3, 15 minutes ago.
You are the Unit I Operator at the Controls (OATC).
The reactivity computer (REACT) is out of service.
Unit I OAC is available.
Preparations are being made to commence a plant cooldown to Mode 5.
Task Standard:
The operator, by completing Enclosure 4.5 of OP/i/A16100/006 (Reactivity Balance Calculation) will determine the Effective Boron Concentration to assure SDM to be 1382 ppm, and identify that the NC System must be borated to this value before the cooldown can be initiated.
Required Materials:
Calculator General
References:
OP/0/A/61 00/006 (Reactivity Balance Calculation), Rev 72 OP/I/A/61 00/SD-I (Prepare for Cooldown), Rev 34 McGuire I Cycle 21 Core Operating Limits Report, Rev 30 OP/i/N6100/022 (Unit 1 Data Book) Cycle 21, Rev 480 2011 Admin-JPMAIaRO NUREG 1021, Revision 9
Appendix C Page 3 of 14 Form ES-C-i Job Performahoe Muf WOrkhéét Handouts:
McGuire I Cycle 21 Core Operating Limits Report OPI0IA6100/006 (Reactivity Balance Calculation), Enclosure 4.5 (Shutdown Margin Unit Shutdown Modes 5, 4 or 3 Without Xenon Credit)
OP/0/A16i00/006 (Reactivity Balance Calculation), Enclosure 4.8 (Fission Product Correction Calculation)
OP/1/A16100/22, Enclosure 4.3, Table 1.15, Cycle 21 Emergency Procedure (EP) Setpoints OP/1/A/6100/22, Enclosure 4.3, Table 6.5, Shutdown Boron Concentration, McGuire I Cycle 21, 1.0% Shutdown Margin OP/1/A16i00/22, Enclosure 4.3, Table 6.5, Shutdown Boron Concentration, McGuire I Cycle 21, 1.3% Shutdown Margin OP/1/A16100/22, Enclosure 4.3, Table 6.7, Shutdown Fission Product Correction, Unit I Cycle 21 OP/1/A/6100/22, Enclosure 4.3, Table 6.10, ARI Differential Boron Worth as a Function of Temperature and Burnup, Unit I Cycle 21 OP/1/A/6100/22, Enclosure 4.3, Table 6.13, Shutdown Boron ARI, McGuire 1 Cycle 21, Required Boron Concentration for 1.0% Shutdown Margin as a Function of Temperature and Burnup.
OP/1/A16100/22, Enclosure 4.3, Table 6.13, Shutdown Boron ARI, McGuire 1 Cycle 21, Required Boron Concentration for 1.3% Shutdown Margin as a Function of Temperature and Burnup.
Initiating Cue:
Based on the information provided to you on the Data Sheet, perform a Shutdown Margin Calculation per OP/0/A/6100/006 Enclosure 4.5 (Shutdown Margin
- Unit Shutdown, Modes 5, 4, or 3 Without Xenon Credit).
Identify whether or not the cooldown can be initiated under the present conditions.
Time Critical Task:
NO Validation Time:
30 minutes 2011 Admin-JPMA1aRO NUREG 1021, Revision 9
Appendix C Page 4 of 14 Form ES-C-i PERFORMAr\\TCEiNFORrirAT1ON (Denote Critical Steps with an asterisk*)
Provide Candidate with Initial ConditionslCue and Data Sheet (Last two (2) Pages of this JPM), and the ten (10) Handouts identified in this JPM.
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT (Step 3.1) If NC Boron concentration> refueling The operator recognizes boron concentration for that the present Boron COLR:
Concentration is NOT (Step 3.1.1) Shutdown greater than Refueling Margin is met.
Boron Concentration, and (Step 3.1.2) Exit this proceeds to Step 3.2.
procedure.
(Operator may check Section 2.15.1 of COLR).
2 (Step 3.2) Record the The operator records Unit 1, following:
Cycle 21, and 200 EFPD (Step 3.2.1) Unit (Information from Data Cycle Sheet)
(Step 3.2.2) Burnup (P1457) 2011 Admin
- JPM Ala RO NUREG 1021, Revision 9
Appendix C Page 5 of 14 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 3 (Step 3.2) Record the following:
(Step 3.2.3) NC System Effective Boron Concentration The operator recognizes (Step 3.2.3.1) IF OAC is that the OAC is available, unavailable and proceeds.
(Step 3.2.3.2) IF OAC is available:
Record B-IC Atom Percent, The operator records 19.8 Best Estimate (P561 3)
(Information from Data Sheet)
Record the Current boron The operator records 1013 concentration (Information from Data Sheet)
Calculate the effective The operator records 1013 boron concentration: (Step ppm (1013 x 19.8/1 9.8 =
3.2.3.2B x Step 3.2.3.2A)/19.8 =
(Step 3.2.3.3) Record the The operator records the effective Boron Effective Boron Concentration:
Concentration as 1013 (Step 3.2.3.1B or Step ppm.
3.2.3.2C) =
4 (Step 3.2.4) Desired NC system temperature for The operator records 33 or shutdown margin 140°F (Information from calculation Data Sheet) 5 (Step 3.2.5) Number of known inoperable RCCAs The operator records 0 (Information from Data Sheet) 2011 Admin
- JPM Ala RO NUREG 1021, Revision 9
Form ES-C-i Page 6 of 14 Appendix C PERFORMANCE INFORMATION S/U COMMENTS STEPS ELEMENTS STANDARD REQUIRED FOR UNSAT The operator recognizes 6
(Step 3.2.6) IF Step 3.2.5>
that Step 3.2.5 is NOT> 0,
° and proceeds.
7 (Step 3.2.7) IF burnup from The operator records 0 step 3.2.2 is > 0 EFPD, (Information from Data record the difference Sheet) between equilibrium and present samarium worth (P1475, Samarium program on OAC or REACT) 8 (Step 3.2.8) IF burnup from The operator recognizes step 3.2.2 is> 12 EFPD that the Unit has been AND unit has been shutdown for 15 minutes shutdown > 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> (Information from Data Sheet), and proceeds 9
(Step 3.3) IF desired, The operator recognizes perform automated that the REACT computer is calculations using NOT available (Information REACT....
from Initial Conditions) 10 (Step 3.4) Manual The operator addresses Calculations Table 1.15 in the Data Book (Step 3.4.1) Stuck Rod and determines the Stuck Boron Concentration:
Rod Boron Concentration to (Step 3.4.1.1) Determine be 172 ppm.
the Stuck Rod Boron Concentration (Data Book Table 1.15)
The operator records fl (Step 3.4.1.2) Record value on Line A of Table 4.5.
in Table 4.5 Line A 2011 Admin-JPMA1aRO NUREG 1021, Revision 9
Appendix C Page 7 of 14 Form ES-C-i PERFORMANCE INFORMAT1OrJ STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT I I (Note prior to Step 3.4.2)
The operator reads the Either the DRPI screen on NOTE and proceeds.
the control board OR the OAC may be used to check control rod position.
- 12 (Step 3.4.2) Shutdown Boron Concentration:
(Step 3.4.2.1) IF both trains of DRPI indicate all rods on bottom, determine the Shutdown Margin Boron Concentration by the following:
The operator determines (Step 3.4.2.1.A) IF Step that Step 3.2.4 is 140°F, 3.2.4 > 200°F and proceeds.
(Step 3.4.2.1.B) IF Step The operator addresses 3.2.4 200°F determine the Table 6.13 in the Data Book required shutdown margin and determines the boron concentration for Shutdown Margin Boron burnup of Step 3.2.2 and Concentration to be 1382 33°F (Data Book Table ppm.
6.13, 1.0% Shutdown Margin).
(Step 3.4.2.1.C) Record The operator records 1382 value in Table 4.5 Line B on Line B of Table 4.5.
(Step 3.4.2.i.D) N/A Step 3.4.2.2 and go to Step The operator will place an 3.4.3.
N/A in 2011 Admin
- JPM Al a RO NUREG 1021, Revision 9
Appendix C Page 8 of 14 Form ES-C-i PERFORMANCE[r.TFORMATIOr\\r STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 13 (Step 3.4.3) All rods in Differential Boron Worth:
(Step 3.4.3.1) Determine the ARI differential boron worth by the following:
(Step 3.4.3.1.A) IF Step The operator determines 3.2.4 > 200°F that Step 3.2.4 is 140°F, and proceeds.
(Step 3.4.3.1.B) IF Step The operator addresses 3.2.4 200°F, determine Table 6.10 in the Data Book the differential boron worth and determines the for burnup of Step 3.2.2 and differential boron worth to lowest tabulated be -9.29.
temperature (Data Book Table 6.10).
The operator records -929 (Step 3.4.3.2) Record value on Line C of Table 4.5.
in Table 4.5 Line C 14 (Step 3.4.4) Zero Power Physics Testing Penalty:
(Step 3.4.4.1) Determine the ZPPT penalty:
If the shutdown margin is being determined after refuel and before ZPPT The operator recognizes (Step 3.4.4.1.B) IF this that this shutdown is being shutdown margin is being performed after the ZPPT, determined after the ZPPT, and that the penalty is 0 the penalty is 0 ppm.
ppm.
(Step 3.4.4.2) Record value The operator records 0 ppm in Table 4.5 Line D on Line D of Table 4.5.
2011 Admin
- JPM Ala RO NUREG 1021, Revision 9
Appendix C Page 9 of 14 Form ES-C-i PERFOR/TANCE INFORMATiON STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 15 (Step 3.4.5) Calculations:
(Step 3.4.5.1) Record The operator records 0 on values of Steps 3.2.5, 3.2.7 Line E of Table 4.5.
and 3.2.8 in Table 45 The operator records 0 on Line F of Table 4.5.
The operator records 0 on Line G of Table 4.5.
(Step 3.4.5.2) Complete Table 4.5, recording 0 for any NAd reference steps.
H = E A (0 172) 0 The operator calculates H and records 0 on Line H of Table 4.5.
The operator calculates I I = F/C (01-9.29) 0 and records 0 on Line I of Table 4.5.
The operator calculates SDM = (B÷D÷G+H)
I =
SDM and records 1382 on (1382+0+0+0) 0 = 1382 Line SDM of Table 4.5.
2011 Admin-JPMAIaRO NUREG 1021, Revision 9
(Step 3.5) Results:
(Step 3.5.1) IF Effective NC Boron Concentration of Step 3.2.3.3 > Table 4.5 or REACT output (Step 3.5.2) IF Effective Boron Concentration of Step 3.2.3.3 <Table 4.5 or REACT Output:
(Step 3.5.2.1) If OAC is available, increase measured NC Boron Concentration to the following value prior to decreasing to or maintaining temperature of Step 3.2.4.
[Table 4.5] x 19.8/Step 3.2.3.2A
[1382] x 19.8/1 9.8 = 1382 (Step 3.5.2.2) IF OAC is unavailable The operator recognizes that the Effective Boron Concentration is <Table 4.5, and proceeds.
The operator identifies that the Effective Boron Concentration must be raised to 1382 ppm before the cooldown can be initiated.
Terminating Cue:
STOP TIME:
Evaluation on this JPM is complete.
Appendix C Page 10 of 14 Form ES-C-i PERRMANCEfNORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 16 20i1 Admin
- JPM Ala RO NUREG 102i, Revision 9
Appendix C Page 1 1 of 14 Form ES-C-i VERIFICATION OFCCMPLET1ON Job Performance Measure No.:
2011 Admin
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result:
SAT UNSAT Examiners Signature:
Date:
2011 Admin
- JPM Al a RO NUREG 1021, Revision 9
Appendix C Page 12 of 14 Form ES-C-i VER[CATtON OF COMPLEflON KEY:
Table 4.5: Shutdown margin Modes 5, 4 or 3 Without Xenon Credit Description Reference Value A. Stuck Rod Boron Step 3.4.1 i72ppm Concentration B. Shutdown Boron Step 3.4.2 1382ppm Concentration C. ARI DBW Step 3.4.3
-9.29 pcm/ppm D. ZPPT Penalty Step 3.4.4 Oppm E. Number of Stuck RCCAs Step 3.4.5 0
F. Duff from Eq Sm Worth Step 3.4.7 Opcm G. Shutdown Fission Product Step 3.4.8 Oppm Worth H. Stuck Rod Penalty E x A Oppm 0 x 172 I. Samarium Adjustment F ÷ C Oppm 0 ÷ -9.29 Shutdown Margin Modes 5,
( B +D + G + H)
I 1382ppm 4or3 (1382+0+0+0)(0) 2011 Admin
- JPM Ala RO NUREG 1021, Revision 9
Appendix C Form ES-C-i JPMCUESHEET DATA SHEET Unit I
Current Cycle 21 Inoperable Control Rod(s)
None Current Power Level 0%
Present NC system temperature 557 degrees Desired NC system temperature 140 degrees Cycle Burnup (P1457) 200 EFPD Present NCS Boron Concentration (sample) 1013 ppm B-b Atom Percent, Best Estimate (P561 3) 19.8 A Samarium from equilibrium (P1475) 0 pcm DRPI Indication (Both Trains)
All rods on Bottom NUREG 1021, Revision 9
Appendix C Form ES-C-i JPM CUE SHEET Initial Conditions:
Unit I was shutdown to Mode 3, 15 minutes ago.
You are the Unit 1 Operator at the Controls (OATC).
The reactivity computer (REACT) is out of service.
Unit I OAC is available.
Preparations are being made to commence a plant cooldown to Mode 5.
INITIATING CUE:
Based on the information provided to you on the Data Sheet, perform a Shutdown Margin Calculation per 0P101A161001006.5 (Shutdown Margin
- Unit Shutdown, Modes 5, 4, or 3 Without Xenon Credit).
Identify whether or not the cooldown can be initiated under the present conditions.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-i Wrkr1eet JPMAIbRO 2011 Admin
- JPM Aib RD (Rev_FINAL)
NUREG 1021, Revision 9
Facility:
Task
Title:
McGuire Calculate Dilution Needed for a Specified Rod Change Task No.:
JPM No.:
2011 Admin
Reference:
Examinee:
GK/A 2.1.25 (3.9/4.2)
NRC Examiner:
Facility Evaluator:
Method of testing:
Date:
Simulated Performance:
Classroom X
Simulator Actual Performance:
Plant X
READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:
Task Standard:
Unit #1 Reactor Power is at 100%, Steady State.
Core burnup is 200 EFPD.
NC Boron Concentration
= 918 PPM.
Present Control Rods Bank D at 215 steps.
Desired Rod Height is Control Rods Bank D at 180 steps.
Dilution of approximately 1407 gallons is calculated within +/- 100 gallons. All critical tasks evaluated as satisfactory.
Required Materials:
Calculator General
References:
OP/1/A16150/009 (Boron Concentration Control), Rev 106 OP/I /A/61 00/022 (Unit 1 Data Book) Cycle 21, Rev 480 OP/1/A/6100/022 (Unit 1 Data Book) Cycle 21, Enclosure 4.3 Section 5.1 Boration and Dilution Tables OP/1/A/6100/022 (Unit 1 Data Book) Cycle 21, Enclosure 4.3Table 6.3.3 Integral Rod Worth in Overlap HFP, Equilibrium Xenon OP/1/A/6100/022 (Unit 1 Data Book) Cycle 21, Enclosure 4.3 Graph 6.11 Differential Boron Worth (HFP, ARC, Eq Xe, Eq Sm)
Appendix C Page 2 of 7 Form ES-C-i JobPerfofmanMeaureWOr1het Handouts:
2011 Admin-JPMA1b RO NUREG 1021, Revision 9
Appendix C Page 3 of 7 Form ES-C-i Job Peormance MeasureWorksheet Initiating Cue:
The CRS has directed you to determine the amount of reactor makeup water needed to obtain the desired Control Rod Height using the McGuire Unit 1 Data Book.
Time Critical Task:
NO Validation Time:
20 minutes 2011 Admin
- JPM Aib RO NUREG 1021, Revision 9
Appendix C Page 4 of 7 Form ES-C-i PERFORMANCE iNFORMATiON (Denote Critical Steps with an asterisk*)
Provide Candidate with Initial ConditionslCue (Last Page of this JPM), and Handout the three listed handouts.
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 1 Operator determines 215 Initial inserted steps integral rod worth reactivity worth =
using the 151-250 EFPD column of 14 pcm OP/1/A161 00/22,.3, Table 6.3.3, IRW in Overlap, HFP, Equilibrium Xe.
- 2 Operator determines 180 Desired Rod height steps integral rod worth inserted reactivity using the 151-250 EFPD worth =
column of OP/i/A/6100/22, 126 pcm.3, Table 6.3.3, IRW in Overlap, HFP, Equilibrium Xe.
- 3 Operator determines the Change in reactivity to change in reactivity be compensated due to required for the rod rod insertion =
insertion 126 pcm
-14 pcm 112 pcm
- 4 Using OP/i /A/6100/22, Operator determines the.3, Graph Differential Boron Worth 6.11 Differential Boron from the graph to be =
Worth (HFP, ARO, Eq
-6.27 pcmlppm Xe, Eq Sm, Unit i Cycle
- 21) determines the Differential Boron Worth for present conditions (200 EFPD) 2011 Admin-JPMAibRO NUREG 1021, Revision 9
Appendix C Page 5 of 7 Form ES-C-i PERFORMANCE INFORMATiON STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR U NSAT 5
Using the Differential Operator determines the Boron Worth and the change in Boron Change in reactivity, Concentration to be =
determines the change in 1121 -6.27 pcmlppm Boron Concentration
=
-17.9 ppm 6
Operator determines Change in Boron =
Boron Concentration 918 18 ppm required 900 ppm
- 7 Using OPI1/A16100122, Using Present Boron.3 Section 5.1 Concentration 918 ppm Boron and Dilution and the Desired Boron Tables, determines the Concentration of 900 Reactor Makeup Water ppm, determines from addition Table that change from 920-900 ppm will require the addition of 1481 gallons of reactor makeup water.
OR Calculation:
67388 x Ln(918/900) =
1334 gallons.
Total Makeup Water to add = 1407 +/- 100 gallons (1307-1 507 gallons).
Terminating Cue:
Evaluation on this JPM is complete.
STOP TIME:
2011 Admin
- JPM Aib RD NUREG 1021, Revision 9
Appendix C Page 6 of 7 Form ES-Cl VERIFICATION OF COMPLETION Job Performance Measure No.:
2011 Admin
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result:
SAT UNSAT Examiners Signature:
Date:
2011 Admin
- JPM Al b RO NUREG 1021, Revision 9
Appendix C Form ES-C-i JPM CUE SI-tEfT INITIAL CONDITIONS:
Unit #1 Reactor Power is at 100%, Steady State.
Core burnup is 200 EFPD.
NC Boron Concentration
= 918 PPM.
Present Control Rods Bank D at 215 steps.
Desired Rod Height is Control Rods Bank D at 180 steps.
INITIATING CUE:
The CRS has directed you to determine the amount of reactor makeup water needed to obtain the desired Control Rod Height using the McGuire Unit 1 Data Book.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-i f
Worksheet JPMA2RO 2011 Admin
NUREG 1021, Revision 9
Appendix C Page 2 of 6 Form ES-C-i Job Performance Measur&Wbrksheet Facility:
McGuire Task No.:
Task
Title:
Use Main Generator Capability JPM No.:
2011 Admin
Reference:
GKIA 2.2.2 (4.6)
Examinee:
NRC Examiner:
Facility Evaluator:
Date:
Method of testing:
Simulated Performance:
Actual Performance:
X Classroom X
Simulator Plant READ TO THE EXANIINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Condifions:
Unft #1 is at 74% reactor power with the following conditions:
Generator load is 840 MWE Power factor is 0.85 lagging Generator Hydrogen pressure s 75 psig Generator voltage is 23.9 KV Power increase to 100% is imminent.
Task Standard:
The operator will select the correct Generator Capability Curve (Curve 3.1.2) and use it to determine the maximum permissible generator load and reactive load. Once completed, the operator will determine the desired voltage per the Generator Voltage Operating Schedule.
Required Materials:
None.
General
References:
OP/i/A16100/022 (Core Data Book), Enclosure 4.3, Curve 3.1.1, Calculated Capability Curve at 95% Voltage (22.8KV)
OP/1/A/6100/022 (Core Data Book), Enclosure 4.3, Curve 3.1.2, Calculated Capability Curve at 100% Voltage (24KV)
OP/i/A/61 00/022 (Core Data Book), Enclosure 4.3, Table 3.1.3, McGuire Nuclear Station Generator Voltage Operating Schedule (kV) 2011 Admin
- JPM A2 RO NUREG 1021, Revision 9
Appendix C Page 3 of 6 Form ES-C-i Job Performar1e MeureWorkheet 0P111A161001022 (Core Data Book), Enclosure 4.3, Table 3.1.4, McGuire Nuclear Station Generator Capability Curve Application Guidance Handouts:
OP/1/A/6100/022 (Core Data Book), Enclosure 4.3, Curve 3.1.1, Calculated Capability Curve at 95% Voltage (22.8KV)
OP/1/A/6100/022 (Core Data Book), Enclosure 4.3, Curve 3.1.2, Calculated Capability Curve at 100% Voltage (24KV)
OP/1/A/6100/022 (Core Data Book), Enclosure 4.3, Table 3.1.3, McGuire Nuclear Station Generator Voltage Operating Schedule (kV)
OP/1/A/6100/022 (Core Data Book), Enclosure 4.3, Table 3.1.4, McGuire Nuclear Station Generator Capability Curve Application Guidance Initiating Cue:
The CRS has directed you to determine the following assuming a power factor of 0.85 is maintained constant during the power increase:
the maximum permissible generator load the maximum reactive load the desired voltage per the Generator Voltage Operating Schedule for todays date/time.
Time Critical Task:
NO Validation Time:
15 minutes 2011 Admin
- JPM A2 RO NUREG 1021, Revision 9
Appendix C Page 4 of 6 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)
Provide Candidate with Initial ConditionslCue, and Handout the Four (4) handouts listed.
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 1 Assuming a power factor of The operator selects Curve 0.85 is maintained constant 3.1.1.
during the power increase, determine the maximum permissible generator load.
Using 0.85 power factor and 75 psig H2 pressure, the operator determines the maximum permissible generator load to be:
1070 Mw (+/-10 Mw)
- 2 Assuming a power factor of The operator selects Curve 0.85 is maintained constant 3.1.1.
during the power increase, determine the maximum Using 0.85 power factor and permissible reactive load.
75 psig H2 pressure, the operator determines the maximum permissible reactive load to be:
- 3 Assuming a power factor of The operator selects Table 0.85 is maintained constant 3.1.3.
during the power increase, determine the desired Using todays time and date voltage per the Generator (Summer, Weekday, Max Voltage Operating Schedule Load), the operator determines the Desired Voltage to be 23.3 KV for Unit#1.
Terminating Cue:
Evaluation on this JPM is complete.
STOP TIME:
2011 Admin
- JPM A2 RO NUREG 1021, Revision 9
Appendix C Form ES-C-i JPM CUE SHEET INITIAL CONDITIONS:
Unit #1 is at 74% reactor power with the following conditions:
Generator load is 840 MWE Power factor is 0.85 lagging Generator Hydrogen pressure is 75 psig Generator voltage is 23.9 KV Power increase to 100% is imminent.
INITIATING CUE:
The CRS has directed you to determine the following assuming a power factor of 0.85 is maintained constant during the power increase:
the maximum permissible generator load the maximum reactive load the desired voltage per the Generator Voltage Operating Schedule for todays date/time. per the Generator Voltage Operating Schedule NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-i Werkreet JPM A4 RO 2011 Admin
NUREG 1021, Revision 9
Appendix C Page 2 of 7 Form ES-C-i Job PerformanoeMeasure Worksheet Facility:
McGuire Task No.:
Task
Title:
Independently Verify Spent Fuel JPM No.:
Exam 2011 Admin Pool Level Adjustment JPM A4 RO K/A
Reference:
GKIA 2.4.34 (4.2)
Examinee:
NRC Examiner:
Facility Evaluator:
Date:
Method of testing:
Simulated Performance:
Actual Performance:
X Classroom X
Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:
The Emergency Plan has been implemented due to an attack on the Facility 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> ago.
The hostile threat has been eliminated and the plant is now recovering, however heavy damage has been sustained.
AP/1/A15500/24 (Loss of Plant Control Due to Fire or Sabotage) has been implemented on Unit 1.
The Standby Makeup Pump is operating to provide inventory to the NC System.
The crew is attempting to maintain Spent Fuel Pool Level greater than minus 2 feet in accordance with Enclosure 4.4 (Spent Fuel Pool Level Control) of OP/1/A16200/005 (Spent Fuel Cooling System).
An operator has been directed to fill the Spent Fuel Pool from the YM System as needed per Step 3.7 of this Enclosure, and is now completed through Step 3.7.2.
Chemistry reports that the last Boron Sample of the Spent Fuel Pool was 2898 ppm.
Task Standard:
The operator will be expected to review Table 4.4-i of Enclosure 4.4 of OP/1/A16200/005 and identify three errors, and make the required corrections.
Required Materials:
None 2011 Admin
- JPM A4 RO NUREG 1021, Revision 9
Appendix C Page 3 of 7 Form ES-C-i Job Performance Measure Worksheet General
References:
OMP 11-1 (Operations Response to a TSC/OSC Activation), Rev 6 AP/1/A/5500/24 (Loss of Plant Control Due to Fire or Sabotage), Rev 28 OP/I /A/6200/005 (Spent Fuel Cooling System), Rev 90 McGuire Unit 1 Cycle 19 Core Operating Limits Report, Rev 30 McGuire Unit 1/2 Technical Specifications Handouts:.4 (Spent Fuel Pool Level Control) of OP/1/A/6200/005 (Spent Fuel Cooling System) completed through Step 3.7.2 as follows:
Step 3.1 Checkbox is checked.
Step 3.2 Initialed/Name of Chemist/Todays Date Step 3.3 NA/Initialed.
Step 3.4 OAC Graphic Aligned Checkbox is checked.
Step 3.5 Section 3.7 Checkbox is checked.
Step 3.7.1 All four Checkboxes checked.
Step 3.7.2 initialed/IV block BLANK.4 (Spent Fuel Pool Level Control) of OP/1/A16200/005 (Spent Fuel Cooling System), Table 4.4-1 completed as follows:
Check Makeup Water Source: RN Checkbox is checked. (ERROR)
Last SFP Boron Sample: 2988 (ERROR)
Initial Spent Fuel Pool Level:
- 1.5 feet Desired Spent Fuel Pool Level: 0.5 feet (ERROR carried forward)
Initiating Cue:
You have been directed to perform an independent verification (IV) ensuring that the total desired SFP Level change is within the guidance of the NOTE in Step 3.7.
Identify any corrections or changes that are needed.
Time Critical Task:
NO Validation Time:
15 minutes 2011 Admin
- JPM A4 RO NUREG 1021, Revision 9
Appendix C Page 4 of 7 Form ES-C-i
- PERFORMANC [NFORMATION (Denote Critical Steps with an asterisk*)
Provide Candidate with Initial ConditionslCue (Last Page of this JPM), and Handout.4 of 0P111A162001005, marked up as described in the Handout Section.
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT (IV for Step 3.7.2) Ensure The operator reviews Table the total desired SFP level 4.4-1 and discovers that the change is within the RN Checkbox is checked guidance of note in Step instead of the YM Checkb9x.
The operator makes this correction on Table 4.4-i.
- 2 (IV for Step 3.7.2) Ensure The operator reviews Table the total desired SFP level 4.4-1 and discovers that the change is within the Last Boron sample was guidance of note in Step transposed incorrectly 3.7.
(should be 2898 ppm rather than 2988 ppm).
The operator makes this correction on Table 4.4-i.
201i Admin
- JPM A4 RO NUREG iO2i, Revision 9
Appendix C Page 5 of 7 Form ES-C-i ERF0AlNFORATtON STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 3 (IV for Step 3.7.2) Ensure The operator reviews Table the total desired SFP level 4.4-i and discovers that the change is within the desired change in level is guidance of note in Step 24 inches, which would be permissible if SFP CB was at the transposed value, but NOT permissible at the actual concentration. (The highest level that the SFP can be raised with the present CB at 2898 ppm is 20-23 inches.
If this level adjustment is permitted, the SFP Level will drop below the COLRITS Value of 2675 ppm value).
The operator identifies that the desired SFP level must be changed to a maximum value of 2-5 inches (maximum level of.2 to.4 ft), and records this on Table 4.4-i in the Desired Spent Fuel Pool Level Block.
Terminating Cue:
Evaluation on this JPM is complete.
STOP TIME:
2011 Admin
- JPM A4 RO NUREG i 021, Revision 9
Appendix C Page 6 of 7 Form ES-C-i VER[FICATIOrctOF COMPLETtON Job Performance Measure No.:
2011 Admin
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result:
SAT UNSAT Examiners Signature:
Date:
2011 Admin
- JPM A4 RO NUREG 1021, Revision 9
Appendix C Form ES.-C-i JPM CUE-SKEET INITIAL CONDITIONS:
The Emergency Plan has been implemented due to an attack on the Facility 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> ago.
The hostile threat has been eliminated and the plant is now recovering, however heavy damage has been sustained.
AP/11A15500124 (Loss of Plant Control Due to Fire or Sabotage) has been implemented on Unit 1.
The Standby Makeup Pump is operating to provide inventory to the NC System.
The crew is attempting to maintain Spent Fuel Pool Level greater than minus 2 feet in accordance with Enclosure 4.4 (Spent Fuel Pool Level Control) of OP/i 1A16200/005 (Spent Fuel Cooling System).
An operator has been directed to fill the Spent Fuel Pool from the YM System as needed per Step 3.6 of this Enclosure, and is now completed through Step 3.6.2.
Chemistry reports that the last Boron Sample of the Spent Fuel Pool was 2898 ppm.
INITIATING CUE:
You have been directed to perform an independent verification (IV) ensuring that the total desired SFP Level change is within the guidance of the NOTE in Step 3.7.
Identify any corrections or changes that are needed.
NUREG 1021, Revision 9